Numerical Analysis of Transient Process of HPR1000 Reactor Coolant Pump Shaft Jamming Accident Condition

Pan Jun; Li Yibin; Qu Zehui; Guo Yanlei; Yang Congxin; Wang Xiuyong

doi:10.13832/j.jnpe.2024.01.0201

Volume 45 Issue 1

Feb. 2024

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Pan Jun, Li Yibin, Qu Zehui, Guo Yanlei, Yang Congxin, Wang Xiuyong. Numerical Analysis of Transient Process of HPR1000 Reactor Coolant Pump Shaft Jamming Accident Condition[J]. Nuclear Power Engineering, 2024, 45(1): 201-209. doi: 10.13832/j.jnpe.2024.01.0201

Citation:

Pan Jun, Li Yibin, Qu Zehui, Guo Yanlei, Yang Congxin, Wang Xiuyong. Numerical Analysis of Transient Process of HPR1000 Reactor Coolant Pump Shaft Jamming Accident Condition[J]. Nuclear Power Engineering, 2024, 45(1): 201-209. doi: 10.13832/j.jnpe.2024.01.0201

Citation:

Pan Jun, Li Yibin, Qu Zehui, Guo Yanlei, Yang Congxin, Wang Xiuyong. Numerical Analysis of Transient Process of HPR1000 Reactor Coolant Pump Shaft Jamming Accident Condition[J]. Nuclear Power Engineering, 2024, 45(1): 201-209. doi: 10.13832/j.jnpe.2024.01.0201

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Numerical Analysis of Transient Process of HPR1000 Reactor Coolant Pump Shaft Jamming Accident Condition

doi: 10.13832/j.jnpe.2024.01.0201

Pan Jun^1
,,
Li Yibin^{1, 2
,
,},
Qu Zehui¹,
Guo Yanlei^{1, 2},
Yang Congxin^{1, 2},
Wang Xiuyong^{1, 2}

1.
School of Energy and Power Engineering, Lanzhou University of Technology, Lanzhou, 730050, China
2.
Key Laboratory of Advanced Pumps, Valves and Fluid Control System of the Ministry of Education, Lanzhou University of Technology, Lanzhou, 730050, China

Received Date: 2023-03-20
Rev Recd Date: 2023-11-01
Publish Date: 2024-02-15

Abstract

Abstract

In order to reveal the pipeline transient mechanism under the shaft jamming accident condition of the reactor coolant pump (RCP), a simplified fluid domain model of the coolant system of the three-loop reactor was established by matching the relationship between the resistance characteristics of the reactor coolant pump and the pipeline of the primary system. Based on the computational fluid dynamics (CFD) method, the actual transient flow process and the real-time change rule of parameters in the reactor coolant system under shaft jamming accident condition were reproduced, and the accident safety evaluation method of reactor coolant system under shaft jamming accident condition was established. The transient changes of main pipeline pressure, wall load of transition bend and pressure of three typical heat transfer tubes with radius of curvature were analyzed under shaft jamming accident condition. The results show that: in the process of the shaft jamming accident, the flow in the accident loop decreases to 0 m³/h and then increases in reverse, and reverse flow occurs. The pressure and wall load of the accident loop and other loops will change dramatically after the shaft jamming accident, and the change degree of the accident loop is greater. The pressure oscillation law of the heat transfer tubes with different curvature radii is basically the same, and the peak pressure of the monitoring point increases gradually along the direction from the inlet to the outlet of each heat transfer tube.
- Reactor coolant pump,
- Shaft jamming accident,
- Pipeline transient mechanism,
- Reactor coolant system,
- Numerical analysis

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References(18)

References

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